Experimental Studies of Reactor Radiation Scattering in the Atmosphere.
Complex Radiochemical and Activation Analysis of Long-life Nuclear Waste Transmutation in Fast Reactors and in the Beams of High Energy Accelerators
Issue of the Monography "Pulsed Reactors in the RFNC-ITP" (final stage of ISTC project 276-96)
System Analysis of Uncertainties of Nuclear Safety Characteristics for VVER Reactors with Various Fraction of MOX Fuel in the Core
Theoretical and Experimental Substantiation of Nuclear Safety for Advanced Pulsed Neutron Sources
Preclinical Neutron Capture Therapy Studies at the MEPhI IRT Nuclear Reactor
Construction of the Subcritical Assembly with Combined Neutron Spectra Driven by Proton Accelerator at Proton’s Energy 660 MeV for Experiments on Long Lived Fission Products and Minor Actinides transmutation (Phase I: Design, Design Documentation and Safe
Experimental Researches of Nuclear-Physics Characteristics of Materials Essential for the Processes of Weapon Plutonium Utilization and Radioactive Wastes Transmutation
Experimental Study of Minor Actinides Transmutation Problem at BFS-73-1 Fast Critical Assembly
Development of experimental Prototype of Equipment and Measuring Technique for Control of Subcriticality of Neutron Multiplying Systems
Fuel Assembly Tests under Severe Accident Conditions
Implementation of an Irradiation Base for Clinical Studies on Neutron Capture Therapy at the IRT MEPhI Nuclear Reactor with use of an Epithermal and Thermal Neutron Beam
Source Term Assessment at Ex-vessel Stage of Severe Accident
Material Science Work Package for Lifetime Extension of VVER-1000 Reactor Pressure Vessels (RPV) from High Nickel Materials
Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel
Scale Experimental Investigation of the Thermal and Structural Integrity of the VVER Pressure Vessel Lower Head in Severe Accident
Study of Fuel Assemblies under Severe Accident Top Quenching Conditions in the PARAMETER-SF Test Series
Phase Relations in Corium Systems
Experimental Study of the Processes at the Corium Melt Retention in the Reactor Pressure Vessel
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ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.